Reactor core-structure re-location modelling for severe nuclear accidents

Lead Research Organisation: Imperial College London
Department Name: Earth Science and Engineering

Abstract

Modern computational codes can be very useful in assessing the behaviour of nuclear power facilities and ensuring that they present minimal hazard to; the public, facility workers and the environment when they enter unintended operating scenarios. This proposal is to develop such methods, as well as to establish a simulation tool that is; accurate, robust, efficient and validated, and able to determine the levels of confidence that we can place on the models. It seeks to help establish advanced computational methods to address problems in fault conditions, as well as to investigate aspects of system behaviour in severe accident situations. It will help provide accuracy that is beyond what is currently possible, and will allow the physics to be explored that cannot be reproduced through experiment. The work proposed here seeks to achieve this by developing a basis for the verification and validation of computational tools against benchmark cases that will then be used to simulate more complex/realistic scenarios. The project will combine the expertise from the UK and Japan, both within academia and industry.

The specific situation that this project intends to investigate is in a civil reactor's response to severe accident scenarios following a loss of its coolant. Under such situations internal structures can be compromised and the melting of control rods and/or fuel pins may occur. In extreme situations whole sections of the core may melt resulting in large quantities of molten materials accumulating in the vessel's lower head. In all these situations the relocation of the core's materials will affect the functioning of the reactor. There is a possibility of achieving a sustained critical reaction, resulting in extensive heating, and the coolant flows will be diverted thus preventing the heat removal from parts of its core. In addition, chemical reactions can occur, some of which pose significant hazards. Examples include oxidation processes between the air and/or steam with the fuel cladding (zirconium in particular) or control rod materials resulting in hydrogen production - as what occurred in Fukushima.

The aims of this project will be to develop a generic framework for accident modelling and validate it through the study of control rod and fuel pin melt. A computer model will be built capable of resolving, in unprecedented detail, the melting, relocating and re-solidification process of the pins when overheated. The objectives are to build the specialist numerical tools that enable the complex physics and chemistry to be resolved. The objective also includes a validation process by a comparison with experiment. This will be through collaboration with academics and industry in Japan.

The outcomes of this work will help scientists and engineers understand the processes during accident and melting scenarios. They will help improve future designs and aid operators' responses to such events. In addition, they will help to enhance safety, limit damage and inform policy makers on design integrity. Importantly, the outcomes of this work will demonstrate to the public our commitment to safety in order to regain or strengthen their confidence in nuclear technology.

Planned Impact

This work will benefit those scientists, government bodies and industries concerned with nuclear power safety. It will also be of interest to those interested in multi-phase flows, structural models, damage models, geological safety of waste repositories and state-of-the-art computational modelling. Specific organisations that will benefit from the modelling and increased understanding include AWE, AREVA, NNL, NDA, HSE, Rolls-Royce, AMEC and EDF (now running UK nuclear reactors). Example areas that will benefit include: nuclear safety, core design analysis, training and decommissioning. It is the research outputs of the kind planned here that is important in view of the central role that nuclear power is expected to play over the coming decades. New reactors and reactor types, and those undergoing life extensions, must meet ever more stringent economic and safety criteria, and assessing their ability to meet these must increasingly rely on advanced computational modelling. The outcome of this research will help determine the strategy for nuclear accident modelling which aims to enhance safety in nuclear reactors. Designers, assessors, regulators and operators of nuclear plants will benefit through better analysis tools, properly validated, which are essential to realize the continuing benefits of nuclear new build. In the unlikely event of an accident the framework proposed here will have helped the scientist and engineers in predicting the events that follow, thus improving their preparations for recovery. It would provide a key component in enabling optimized mitigation strategies to be developed during an evolving accident.

Society will also benefit from the economical and carbon-free energy that nuclear plants provide as well as reassurance that the science and tools behind their safety are of the highest quality. This in turn will help improve public confidence and perception of nuclear safety. The economic impacts will be seen from the potential use of the software and associated consultancy, both within the UK and abroad, and in the prevention of overseas codes dominating the market. The impacts also include addressing the urgent need to train scientists and engineers, at all levels including doctoral and postdoctoral levels, to undertake the necessary activities for the next generation of nuclear power. Besides the research outputs, programmes like this are valuable in training such people.

This work will also be of interest to wider EPSRC and NERC communities. For the EPSRC community, areas where our work will be of benefit include: plasma physics, nuclear waste modelling, industrial processing, combustion, chemical and catalyst applications, and oil and gas. NERC communities will benefit from this next generation multi-phase technology for research in predictive flows in atmospheres and oceans. Many of the techniques and tools we will be working on are also of interest to the wider computational physics community. There is strong potential for their re-application to resolve other physical phenomena using the general adaptive discretisations and solver technologies. There is also a strong interest in using this software for multi-phase simulations of nuclear systems in National Laboratories including those in the USA, France and Japan, where our researchers have acted as consultants often using our models.

Publications


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Lei Q (2015) Polyaxial stress-induced variable aperture model for persistent 3D fracture networks in Geomechanics for Energy and the Environment
P Nicholas Smith, (2017) Directions in Radiation Transport Modelling in Multiphysics
Salinas P (2016) Improving the convergence behaviour of a fixed-point-iteration solver for multiphase flow in porous media in International Journal for Numerical Methods in Fluids
Yang P (2017) The immersed-body gas-solid interaction model for blast analysis in fractured solid media in International Journal of Rock Mechanics and Mining Sciences
 
Description 1. Developed a new generation dynamic core for nuclear safety and accident analysis that uses adaptive unstructured mesh solvers with parallel architectures so as to reduce the emphasis on the user specifying numerical resolution or mesh. Key to nuclear safety modelling, the dynamic core determines numerical and modelling errors which are necessary to determining the level of confidence we can place in a nuclear safety model.
2. Enhanced physics models by including chemistry models and novel immersed structure models (control rods, fuel pins etc.) that provide improved techniques for resolving interactions (heat, mass, momentum exchanges) between solids, liquids and gases.
3. Demonstrated accuracy and efficiency for key severe accident problems, that of direct relevance to the Fukushima accident, involving control rod and fuel pin melt, and validated model results against physical experiments.
4. Trained PDRAs in reactor fault studies/nuclear safety and maintained a research group that is acknowledged internationally (evidenced by our consultancy with and work for major international nuclear labs throughout the world) as a centre of nuclear multi-physics expertise.
5. Maintained and enhanced industrial, government and national and international academic contacts by improved dissemination routes to industry, international research laboratories, academia and the public.
Exploitation Route This work is of broad interest to those scientists and organisations concerned with the safe production of nuclear power and aims to serve a large proportion of the industrial bodies associated with the UK's and Japan's nuclear sector, as well as the broader international bodies. Examples include AREVA, AMEC, NNL, NDA, HSE, EDF Energy (UK), the University of Tokyo, Hitachi-GE, JAEA (Japan) and IRSN (France), all of whom can benefit from these advanced severe accident technologies in areas of nuclear safety and, potentially in the future, safe decommissioning activities. Our steering group has been set up to include representatives from many of these industrial bodies in order to advise and monitor progress and ensure the work remains focused on industrial current and future needs. The steering panel also consists of individuals that bring the necessary expertise to exploit the novel technologies and deliver an easy to use model for applications ranging in the aforementioned disciplines. This has bridged the gap between industry users, academics and the software houses that market these products. A route to market within the European nuclear sector has already been identified in collaboration with IRSN, where the code will be integrated within their world leading accident modelling framework ASTEC. A second route is through AMEC who will oversee the licensing of the code to individual customers and particularly versions of the model that have been through a quality assurance process. Two stages of code release were envisaged:
Stage 1: A basic release for multi-phase modelling of pins and control rods that satisfies the needs of a large proportion of the potential users has been developed. Students from the University of Tokyo have been using it.
Stage 2: The techniques for modelling chemistry and radiative heat transfer will soon be incorporated. Much of the advanced research contained here will take time to be integrated into this release, and so we will work on a two-year time scale to integrate our work into the software.
Sectors Energy,Environment
 
Description Collaborative project on severe nuclear accident with Tokyo University 
Organisation University of Tokyo
Country Japan 
Sector Academic/University 
PI Contribution The UK part of the project developed a computational framework that may be used across a range of severe accident applications. The technology is based on the FETCH model, which has world leading numerical technologies for simulating complex nuclear engineering problems. Specifically, this project developed the model's use for analysing nuclear accident scenarios including; control and fuel pin melt and re-solidification.
Collaborator Contribution Tokyo university performed physical experiments of BWR control blades melting. They also performed numerical simulations using particle-based methods.
Impact We have extended the FETCH modelling framework so that it can simulate nuclear accidents. We have written 4 joint journal papers with our Japanese collaborators and another 5 journal papers. In addition, we set up the UK steering committee on severe nuclear accident research.
 
Description ASTRID seminar 2017 
Form Of Engagement Activity A talk or presentation
Part Of Official Scheme? No
Geographic Reach International
Primary Audience Professional Practitioners
Results and Impact seminar presentation to nuclaer industry and academia (international) covering elements of accident progression.
Year(s) Of Engagement Activity 2013,2017